Development of continuous-energy sensitivity analysis capability in OpenMC
Name
Forget_Development of continuous.pdf
Description
Accepted version
Size
1.77 MB
Format
Unknown
Checksum (MD5)
0cf623d9b89295600964dca7a1dae107
Author(s)
Peng, Xingjie
Liang, Jingang
Alhajri, Abdulla Abdulaziz
Forget, Benoit Robert Yves
Smith, Kord S.
Date Issued
2017
Journal
Annals of Nuclear Energy
Publisher
Elsevier BV
Version
Author's final manuscript
Abstract
© 2017 Elsevier Ltd The iterated fission probability (IFP) method and the Contributon-Linked eigenvalue sensitivity/Uncertainty estimation via Track length importance CHaracterization (CLUTCH) method have been implemented in several Monte Carlo codes to perform sensitivity calculations. In this work the unified adjoint and generalized adjoint calculation framework combining the IFP method and the CLUTCH method is proposed, and corresponding capabilities for calculating nuclear data sensitivity to the effective multipilication factor and reaction rate ratios are implemented in OpenMC. Results are presented on Godiva, Jezebel and a PWR fuel pin system which demonstrate that OpenMC results agree well with reference direct perturbation sensitivity coefficients. In addition, two main problems of the IFP method related to the number of latent generations, namely convergence and statistical fluctuations are investigated theoretically and numerically. This paper further demonstrates that the fission matrix approach is better suited to generate the adjoint and generalized adjoint source distribution in the CLUTCH method to overcome the drawbacks of the IFP method.
MIT Department
Massachusetts Institute of Technology. Department of Nuclear Science and Engineering
Terms of Use
Creative Commons Attribution-NonCommercial-NoDerivs License
Persistent DSpace Link
DOI of Published Version
https://doi.org/10.1016/J.ANUCENE.2017.06.061
